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ACI-318 +, ACI-349 +  and ACI-307 +

ANSI B31.1 +, ANSI N13.1-1969 +, ANSI N13.10-1974 +, ANSI B16.5 +, ANSI B31.7 +, ANSI B31.1.0 +, ANSI B16.11 +, ANSI/ANS-56.8-1994 +  and ANSI B31.1.0 - 1967 +

ASME Section XI +, ASME Section III +, ASME Section IX +, ASME Section II +  and ASME Section VIII +

Boron +, Iodine +, Uranium +, Iron +, Nickel +, Krypton +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Xenon +, Chloride +, Lead +, Helium +, Aluminum +, Mercury +, Zinc +, Hafnium +  and Platinum +

10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +, 10 CFR 72 +, 10 CFR 54 +, 10 CFR 20.1301 +, 10 CFR 50.49 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +, 10 CFR 54.3 +, 10 CFR 20.1 +, 10 CFR 50.55a +  and 10 CFR 70.24 +

H.2(s) +  and H.2(e) +

05000321  +, 05000366  +, 00367  +, 00259  +, 00260  +, 00277  +, 00278  +  and 00321  +

Drawing 7.1-2 +, Drawing 4.10-6 +, Drawing 7.5-7 +, Drawing 7.5-13 +, Drawing 7.16-1 +, Drawing 7.19-2 +  and Drawing 10.7-1 +

May 21, 1971  +  and March 22, 1997  +

Orenak M D +  and Plant Licensing Branch II +

GDC 61 +, GDC 18 +, GDC 64 +, GDC 62 +  and GDC 19, Control room +

NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent +  and NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +

ML17010A336 +, ML17010A336 +, ML17010A336 +, ML17010A336 +, ML17010A336 +, ML17010A336 +, ML17010A336 +, ML17010A336 +, ML17010A336 +  and ML17010A336 +

IEEE 383 +, IEEE 344 +, IEEE 323-1974 +, IEEE 279 +, IEEE 384-1974 +, IEEE 279-1971 +, IEEE 308 +, IEEE 344-1975 +  and IEEE 317 +

IP 2815 +  and IP 2809 +

Co-60 +, Cs-137 +, Sr-90 +, Y-90 +, Kr-85 +, I-131 +, N-16 +, Nitrogen-16 +, Mo-99 +, Cobalt-60 +  and Mn-54 +

Westinghouse +, General Electric +  and Chicago Bridge & Iron +

NRC Bulletin 80-11 +, NRC Bulletin 79-14 +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

NUREG-1048, Forwards Safety Evaluation Supporting Proposed Turbine Sys Maint Program Submitted w/870513 Ltr +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

ES +, MP +, SAP +, SP +, ISP +  and Emergency Plan +

Regulatory Guide 1.97 +, Regulatory Guide 1.9 +, Regulatory Guide 1.105 +, Regulatory Guide 1.26 +  and Regulatory Guide 1.89 +

NEDC-32749P +, NEDO-10174 +, NEDC-33085P +, NEDO-10173 +, NEDE-11146 +, NEDC-30474 +, NEDE-22224 +, NEDO-10017 +, NEDO-10029 +, NEDO-10045 +, NEDO-10139 +, NEDO-10179 +, NEDO-10208 +, NEDO-10189 +, NEDE-22223 +, NEDC-32014P +, NEDO-10320 +, NEDC-20566P +, NEDC-32410P +, NEDE-22154 +, NEDC-30039 +, NEDE-10017 +, NEDO-24570 +, NEDO-2188 +, NEDO-32205 +  and NEDC-30997 +

1E-5 +, 1Z41-B003A +, 1Z41-B003B +, 2E-6 +, 4E-4 +, 2E-3 +, 9E-5 +, 9E-3 +, 1E21-F006A +, 2E-1 +, 9A-Appling +, 9B-Appling +, 1T48-F342A-L +, 7E-1 +, 07-95-100 +  and 133B-3 +

Manual Scram +  and Automatic Scram +

Tennessee +, Pennsylvania +, Georgia +, Maryland +, Washington +, California +, South Carolina +, Idaho +  and Vermont +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Emergency Response Data System +, Shutdown Cooling +, Reactor Recirculation Pump +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Remote shutdown +...

Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Ultimate heat sink +, Grab sample +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Weld Overlay +, Hydrostatic +, Coatings +, Operating Basis Earthquake +, Nondestructive Examination +, Operator Manual Action +, Squib +, Water level shrink +, Emergency Lighting +, Incorporated by reference +, High Energy Line Break +, Tornado-Generated Missile +, Aging Management +, Abnormal operational transient +, Design basis earthquake +, Feedwater Heater +, Scram Discharge Volume +, Annual Radiological Environmental Operating Report +...

J-73-39 +  and F-H21-P405A +